ML020300299

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RAI Letter
ML020300299
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 02/07/2002
From: Wang A
NRC/NRR/DLPM/LPD4
To: Ridenoure R
Omaha Public Power District
Wang A, NRR/DLPM, 415-1445
References
TAC MB3654
Download: ML020300299 (4)


Text

February, 7, 2002 Mr. R. T. Ridenoure Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

Post Office Box 550 Fort Calhoun, NE 68023-0550

SUBJECT:

FORT CALHOUN STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MB3654)

Dear Mr. Ridenoure:

The NRC staff has reviewed your amendment request dated December 14, 2001, and has determined that additional information is needed to complete our review. Enclosed is a request for additional information regarding the December 14, 2001, submittal. Please respond within 30 days of receipt of this letter. This request has been discussed with Richard Jaworski of your staff and he has agreed to this schedule. If you have any questions regarding this request, please contact me at (301) 415-1445.

Sincerely,

/RA/

Alan B. Wang, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-285

Enclosures:

Request for Additional Information cc w/encls: See next page

Ft. Calhoun Station, Unit 1 cc:

Winston & Strawn ATTN: James R. Curtiss, Esq.

1400 L Street, N.W.

Washington, DC 20005-3502 Mr. Jack Jensen, Chairman Washington County Board of Supervisors Blair, NE 68008 Mr. Wayne Walker, Resident Inspector U.S. Nuclear Regulatory Commission Post Office Box 309 Fort Calhoun, NE 68023 Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 Ms. Julia Schmitt, Section Administrator Nebraska Health & Human Services Systems Division of Public Health Assurance Consumer Services Section 301 Cententiall Mall, South P. O. Box 95007 Lincoln, Nebraska 68509-5007 Mr. Richard P. Clemens Manager - Fort Calhoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant Post Office Box 550 Fort Calhoun, NE 68023-0550 Mr. Mark T. Frans Manager - Nuclear Licensing Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

Post Office Box 550 Fort Calhoun, NE 68023-0550

February 7, 2002 Mr. R. T. Ridenoure Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.

Post Office Box 550 Fort Calhoun, NE 68023-0550

SUBJECT:

FORT CALHOUN STATION, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION (TAC NO. MB3654)

Dear Mr. Ridenoure:

The NRC staff has reviewed your amendment request dated December 14, 2001, and has determined that additional information is needed to complete our review. Enclosed is a request for additional information regarding the December 14, 2001, submittal. Please respond within 30 days of receipt of this letter. This request has been discussed with Richard Jaworski of your staff and he has agreed to this schedule. If you have any questions regarding this request, please contact me at (301) 415-1445.

Sincerely,

/RA/

Alan B. Wang, Project Manager, Section 2 Project Directorate IV Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-285

Enclosures:

Request for Additional Information cc w/encls: See next page DISTRIBUTION:

PUBLIC PDIV-2 Reading RidsNrrDlpmPdiv(SRichards)

RidsNrrPMAWang RidsNrrLAEPeyton RidsOgcRp RidsACRSACNWMailCenter WBateman ACCESSION NO. ML020300299 NRR-088 OFFICE PDIV-2/PM PDIV-2/LA PDIV-2/SC NAME AWang:sp EPeyton SDembek DATE 2/6/02 2/1/02 2/7/2002 OFFICIAL RECORD COPY

REQUEST FOR ADDITIONAL INFORMATION OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1 DOCKET NO. 50-285 By letter dated December 14, 2001, Omaha Public Power District (OPPD/licensee) proposed to apply ASME Code Case N-640, to Appendix G to Section XI of the ASME Boiler and Pressure Vessel Code, as the underlying basis for the establishment of the pressure-temperature (P-T) limit curves. The proposed technical specification change seeks to employ a single P-T limit curve for the reactor pressure vessel heatup and cooldown. This single heatup/cooldown P-T limit curve is a composite curve generated from the most limiting pressure for a given temperature from a 100-F/hr cooldown curve (above 178-F), 50-F/hr cooldown curve, 75-F/hr heatup curve, and an isothermal curve. The NRC staff requires the following information to complete our review of your submittal.

For each curve (the 100-F/hr cooldown curve, the 50-F/hr cooldown curve, the 75-F/hr heatup curve, and the isothermal curve) used to develop the composite heatup/cooldown curve, provide the following data for each temperature point given in Table 1 of Westinghouse letter LTR-PS-01-26, Rev. 00:

KIm - the crack tip stress intensity due to membrane (pressure) stresses for the 1/4 T and 3/4 T flaws; KIt - the crack tip stress intensity due to thermal stresses for the 1/4 T and 3/4 T flaws; KIc - the material fracture toughness at the crack tip of the 1/4 T and 3/4 T flaws; T1/4T - the reactor pressure vssel (RPV) metal temperature at the tip of the 1/4 T flaw; and T3/4T - the RPV metal temperature at the tip of the 3/4 T flaw.